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-ray from actinides in various types of spent fuelsMorita, Yasuji; Tsubata, Yasuhiro
no journal, ,
Energy emission by -ray from actinides was evaluated for various types of spent fuels (SF) to compare absorbed doses of solvents by -ray in extraction process. The spent fuels evaluated in the present study were LWR UO
fuel, LWR MOX fuel, FBR fuel with U and Pu (FBR(Pu)) and FBR fuel with MA recycle (FBR(MA)). When the solvent contains 0.4 M of U and Pu as the total concentration, the adsorbed dose rate of the solvent by -ray from the extracted U and Pu was 0.016 Gy/s for LWR UO fuel cooled for 5 years. The dose rate for LWR-MOX, FBR(Pu) and for FBR(MA) was 6.4 times, 16.4 times and 15.8 times higher than that for LWR-UO, respectively. The absorbed dose rate of the solvent which contains Am, Cm and rare earth elements with the total concentration of 0.04 M was 0.071 Gy/s for 5-year cooled LWR-UO and 0.74 Gy/s for LWR-MOX.
Taguchi, Shigeo; Surugaya, Naoki; Kurosawa, Akira; Watahiki, Masaru
no journal, ,
no abstracts in English
Nagaoka, Shinichi; Kawaguchi, Yoshihito
no journal, ,
In Tokai Reprocessing Plant (TRP), 50
60% of Np is transferred to waste. To co-recover Pu-U-Np, the large ratio of Np transition to waste is problem. So we are investigating Np behavior with extraction cycles in TRP to obtain control technology for Pu-U-Np co-recovery. Now we present Np behavior in TRP and plan of research co-recovery of Pu-U-Np.
Nakahara, Masaumi; Sano, Yuichi; Nomura, Kazunori
no journal, ,
Using the advanced aqueous reprocessing system named NEXT, it was attempted to co-reocver Np with U and Pu by TBP in a simplified solvent extraction process. In this study, we conducted two counter current experiments with TBP for enhanceing the Np oxidation to extractable Np(VI) and its extraction; one was a feed solution with a high nitric acid concentration and the other was used a scrubbing solution with a high nitric acid concentration. In this condition, these flow sheets showed the large contribution of nitric acid concentration at the extraction section to Np oxidation and extraction, and the effectiveness of high nitric acid concentration in the feed solution, which might be bring the acceleration of the Np oxidation in the feed solution as well as at the extraction section in the centrifugal contactors.
Arai, Yoichi; Takeuchi, Masayuki; Koizumi, Tsutomu; Kase, Takeshi; Kato, Toshihiro*
no journal, ,
no abstracts in English
Kimura, Takashi
no journal, ,
no abstracts in English
Mizuguchi, Koji; Yasuike, Yoshiyuki*; Fukushima, Mineo; Myochin, Munetaka
no journal, ,
no abstracts in English
Shimizu, Takenori
no journal, ,
TRP was designed 1970s to reprocess nuclear spent fuel mainly from domestic LWR and ATR Fugen. It was necessary to challenge many requirements for steady operation of plant due to mechanical troubles in head end process, acid corrosions of dissolver vessel and evaporator tubes, strict environmental restriction to release activity, and reduction of waste volume. Through these solutions, the maturity of current reprocessing technology was achieved. TRP reprocessed 1105 tons of UO with 23 tons of ATR MOX by Nov. 2006. The technologies such as U Denitration, Pu U Co conversion, HLW Vitrification and Radiation Control and so on that TRP developed are used for RRP of JNFL. TRP is continuing personnel support for RRP by sending 130 TRP engineers and training RRP engineers. Personnel training and education of TRP is conformed to ISO9000 System, and the procedure is ruled in Operational Safety Program of TRP.
Funasaka, Hideyuki
no journal, ,
In this session, the following three subject have been disucussed. Current status and perspective of FR cycle technology development in Japan. The securing of young personnel resources and advance personnel training. The continuing the present technology to the next generation.
Kurata, Masaki*; Yahagi, Noboru*; Kitawaki, Shinichi; Fukushima, Mineo
no journal, ,
no abstracts in English